Effects of fuel rod length on in-core relocation of liquefied material

Journal Article · Sat Jan 01 00:00:00 EST 1983 · AIChE Symp. Ser.; (United States)

OSTI ID:5491544

Haggag, F M; Siefken, L J

Severe fuel damage experiments are being conducted in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory. Since the fuel rods used in PBF experiments are short (0.9144 m) compared to those used in commercial reactors (3.658 m), the influence of fuel rod length on the relocation of liquefied fuel rod material during a severe reactor accident was studied. The LIQSOL model of the Severe Core Damage Analysis Packed (SCDAP) code was used to calculate the motion of molten material, the rate of solidification, the crust axial profile, and the coolant flow channel blockage. These calculations were performed for two hypothetical accidents; one in a core having short test fuel rods and the other in a core with commercial-size fuel rods. The results, presented in this paper, indicate the severe fuel damage experiments, using short test fuel rods, can be used to understand the relocation of liquefied fuel rod material in commercial reactors.

• Research Organization: EG and G Idaho Inc.
• DOE Contract Number: AC07-81ID12317
• OSTI ID: 5491544
• Journal Information: AIChE Symp. Ser.; (United States), Vol. 79:225
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PBF REACTOR
FLUID-STRUCTURE INTERACTIONS
FUEL RODS
REACTOR CORES
FUEL ELEMENT FAILURE
LENGTH
REACTOR CORE DISRUPTION
REACTOR SAFETY
ACCIDENTS
DIMENSIONS
FUEL ELEMENTS
PULSED REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
TANK TYPE REACTORS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors